ML20087P023
| ML20087P023 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/18/1984 |
| From: | Boyer L, Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NLS-84-015, NLS-84-15, PROC-840118, NUDOCS 8404050380 | |
| Download: ML20087P023 (16) | |
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.e CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 REVISED PLANT EMERGENCY PROCEDURES SECTION NINBER TITLE REVISION NIMBER 2.1* Initial Emergency Actions 10 2.6.5 Representative At The State Emergency Team Headquarters 2 3.6.1* Release Estimates Based Upon Stack / Vent Readings 6
- Partial Instruction or Modification (9281WRMpgp) 8404050380 840118 PDR ADOCK 05000324 F pyg i
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CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 INITIAL EMERGENCY ACTIONS PLANT EMERGENCY PROCEDURE: PEP-02.1 VOLUME XIII Rev. 010 Recomunended By: s- Date:
Director - A
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et 33 istrative Support .
Approved By: c0.,_. Date: ,2./,e(Y3 General Mamtger # '
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LIST OF EFFECTIVE PAGES PEP-02.1 Pame(s) Revision ,
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s BSEP/Vol. XIII/ PEP-02.1- i~. Rev. 10 s
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l Section 3 - Abnormal Core Conditions and Fuel Damage 3.1 Unusual Event Failed fuel as indicated by:
3.1.1 Liquid
- a. Reactor Coolant System (RCS) activity greater than 4.0 pCi/ml I-131 dose equivalent.
- b. RCS activity greater than 0.2 pCi/ml I-131 dose equivalent but less than limit above for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- c. RCS activity greater than 100/5 pCi/ml for all isotopes.
3.1.2 Gaseous
- a. Condenser off-gas radiation monitor (D12-RM-K601 A & B) reading of greater than 1.2 x 10' mR/hr.
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- b. An increase of greater than 2.4 x 10 mR/hr in 30 minutes l on the condenser off-gas radiation monitor (D12-RM-K601 A & B).
3.2 Alert 3.2.1 Liquid .
Reactor coolant activity greater than 40 pCi/ml I-131 dose --
equivalent.
3.2.2 Gaseous Condenser off-gas radiation monitor (D12-RM-K601 A & B) reading 5
of greater than 1.2 x 10 mR/hr.
I 3.3 Site Emergency 3.3.1 Reactor Coolant System activity is-greater than 400 pCi/ml I-131 dose equivalent.
3.4 General Emergency 3.4.1 Reactor Coolant System activity is greator than.4000 uCi/ml I-131 dose equivalent.
3.4.2 Loss of any two of the three-fission product barriers below:
- a. Failed fuel causing RCS' activity greater than 40 pCi/ml.
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'BSEP/Vol. XI'II/ PEP-02.1 11 Rev~ 10'
EMERG YACTbN EVELS
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Section Event Category Page No.
1 Abnormal Primary Leak Rate 8 2 Steam Line Break or Safety / Relief 9 Valve Failure 3 Abnormal Core Conditions and Fuel Damage 11 4 Abnormal Radiological Effluent or 13 Radiation Levels 5 Loss of Shutdown Functions: Decay Heat 16 and Reactivity 6 Electrical or Power Failures 18 7 Fire 19 8 Control Room Evacuation 20 9 Loss of Monitors or Alarms 21 10 Fuel Handling Accident 22 11 Security Threats 23 12 Injury or Specific LCOs 24 i 13 Hazards to Plant Operations 25 14 Natural Events 26 15 Shift Operating Supervisor / Site Emergency 27 Coordinator Judgments CAUTION ,
The following flow charts (pages 5, 6, and 7) should be used as an -
initial check that an emergency action level has been met or exceeded.
The specific indications for classifying an emergency begin on page 8.
BSEP/Vol. XIII/ PEP-02.1 4 Rev. 10
CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PIANT UNIT 0 REPRESENTATIVE AT THE STATE EMERGENCY RESPONSE TEAM HEADQUARTERS PLANT EMERGENCY PROCEDURE: PEP-02.6.5 i
VOLUME XIII
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Rev. 002 Reconnended By: .Ah _ Date: 12.!2e f.33 -
, Director - Admin ative Support Approved By: C D . '_ -a- 'Date : 3 r /36 /m General Manager /
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1.0 Responsibilities and Objectives The member of the plant staff identified in PEP-01 as SERT representative is responsible to the Emergency Response Manager for: l 1.1 Reporting to the SERT Headquarters as directed by the Site Emergency Coordinator / Emergency Response Manager.
1.2 Providing liaison with agency representatives at the SERT Headquarters.
1.3 Serving as director of CP&L's involvement with off-site protective actions during a declared emergency.
2.0 Scope and Aoplicability This procedure shall be implemented during a declared site or general emergency. The actions and responsibilities are limited to the individuals listed in PEP-01 as SERT Reprssentative and those emergency l team members assigned to them.
3.0 Actions and Limitations 3.1 General Requirements 3.1.1 Report your position and readiness to the Site Emergency Coordinator or the Emsrgency Response Manager.
C 3.1.2 Announce your name and assumed position title to all appropriate agency representatives at the State Emergency Response Team Headquarters. ,
3.1.3 When relinquishing this position, brief your successor on the emergency and emergency actions status.
3.1.4 Date:mine need for additional equipment, supplies, and manpower and make request for the same.
3.1.5 Initiate a log and ensure documentation of the following g in accordance with PEP-04.1, Record Keeping and Documentation: .
3.1.5.1 Communications Key decisions 3.1. 5 . 2 3.1.5.3 Data collected 3.1.5.4 Checklists 3.1.6 Ensure proper use of communications equipment per l PEP-03.1.3, Use of Communications Equipment.
ESEP/"ol. XIII/ PEP-02.5.5 1 P.ev. 2
a 3.2 Relay Site Emergency Coordinator's/ Emergency Response Manager's recommendations for protective actions off site to agency C representatives at the SERT Headquarters.
3.3 Provide descriptions of the procedures used to analyze samples so that differences in analysis methods are not, of themselves, the cause of differing assessments of levels'of radioactivity in the environment (i.e., may result from use of different types of TLDs and different methods of reading TLDs).
. 3.4 Where requested, coordinate arrangements for analysis of replicate samples.
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l L ' 3 SIP /*.'ol. XIII/FEP-02.6.3 - 2 Rev.'2 b
4 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 RELEASE ESTIMATES BASED UPON STACK / VENT READINGS 1
PLANT EMERGENCY PROCEDURE: PEP-03.6.1 VOLUME XIII ,
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' Recommended By: N/- - Date: s/ 2Afi3 l Director - Admin p rative Support
, Approved By: C hi N Date: s2./yo / f 7 l General Man #ger / /
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- LIST OF EFFECTIVE PAGES
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1.0 Responsible Individual and Objectives
( The Radiological Control Director is responsible to the Site Emergency Coordinator for determining the magnitude and rate of radioactive release to the environment. The Radiological Control Director may delegate the calculational aspects of this procedure to the Dose Projection Coordinator. This procedure may be used by the Control Room personnel until the dose projection team is activated in the Technical Support Center.
2.Q Scope and Aeplicability This procedure shall be implemented by the Site Emergency Coordinator, or by the Radiological Control Director, whenever an abnormal radiological release through an identifiable release point is suspected, including any Site or General Emergency. The only apparatus required is a scientific calculator.
3.0 Actions and Limitations
, NOTE: The detector response will depend on the specific isotopic mixture being released at various times. Grab samples must be taken, analyzed and evaluated to provide an exact relationship; however, the predetermined relationchip used in this procedure should be sufficiently accurate to guide initial emergency response actions and assessments.
( Lisc of EXHIBITS:
3.6.1-1 Source Term Calculation from Plant Stack Moniters 3.6.1-2 Source Term Calculation from #1 RX Gas (1-CAC-AQH-1264-3) ,
3.6.1-3 Source Term Calculation from #1 Turbine Vent 3.6.1-4 Source Term Calculation from #2 Rx Gas (2-CAC-AQH-1264-3) 3.6.1-5 Source Term Calculation from #2 Turbine Vent 3.6.1-6 Estimating Stack Flow 3.1 Depending upon alarming channel (s), use appropriate EXHIBIT (EXHIBIT 3.6.1-1 through EXHIBIT 3.6.1-5) to calculate the release source term.
Note: If the time dur.ation of the release is unknown, assume 60 minutes and perform this procedure as directed by the Radiological Control Director.
3.2 If only one channel 'is alarming or reading abnormally high, the source term determined on the appropriate EXHIBIT is the total.
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l LL ESEP/7:1. XIII/ PEP-03.6.1 1 .Tev. 6 l
d EXHIBIT 3.6.1-1 h SOURCE TERM CALCULATION FROM STACK MONITORS Release rate is read in pCi/sec directly from 2-D12-RR-4600 (effluent channel) hen the 2-VA-FT-3359 flow instrument loop is operational. The following alculations are necessary when this loop is not operational.
CONVERSION 1
MONITOR FACTOR RELEASE READING FLOW. 8 cc/sec RATE 8
TIME (pCi/ce) (cfm) cfm (pCi/sec) 472 e
The monitor automatically selects the most accurate operational channel, either low, mid, or high range. Read the pCi/cc from the appropriate channel (low, mid, or high) of 2-D12-RR-4599.
If not available, use the sum of design flows for systems exhausting to
} the stack as per Exhibit 3.6.1-6.
- Release rate (pCi/sec) = pCi/cc X cfm X 472 ,
. 3SEP/Vol. XIII/ PEP-03.6.1 3 Rev. 6
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N EXHIBIT 3.6.1-6 *
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~, ESilHATING STACK FLOW ,
D SUM THE DESIGN FLOWS FOR SYSTEMS EX11AUSTING TO THE STACK.
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!"i CASEOUS RADWASTE UNIT NO. 1 E C
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[FilUENT LlHITS W .-SJAE L-SJAE A
B 300 300 hoMINDELAYl
!j -TURB GLAND SEAL A 650 s r' -TURB GLAND SEAL 8 650 o --- I -MECH VAC PUNP A 1810
'. 1.8 MIN DELAY -44ECil VAG PUNP B 1810 os r-OW PURGE A 7200
_, L-0W PURGE B 7200 MAIN r-6TANDBY GAS TRAIN A 3500 STACK a-STANOBY CAS TRAIN 8 3500 UNIT No 2 3A0GI W AE A 300 M l30 MIN DELAY l L-SJAE B 300
-TURB GLAND SEAL A 650
-TURS GLAND SEAL 8 650 1 08
-NECH VAC PUMP A 1810 i 1 3_jg 1 pCLAY_ <-MECH VAG PUMP B 1810 !
-),yi....O r-DW PURGE A 7200 ;
W PURGE B 7200 .
lli-r-STANDBY CAS TRAIN
'-STANDBY CAS TRAIN A
B 3500 3500 i
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COMMON
. _ . r-RADWASTE BLDG FAN A 23200 i 5-RADWASTE BLDG FAN 8 23200
- A0G BLDG VENT EXH 18000 g
i TOTAL STACK EFFLUENT FLOW
" Al lllOUCli lilERE ARE TWO SUPPLY AND DotAUST FANS THIS FLOW IS BASED ON ONE SUPPLY AND ONE EXHAUST FAN RUNNING BY PROCEDURE. t 4
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E NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 kg . . . . . ,o/ March 26, 1984 50-324/325 Brunswick MENORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Divison of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The submitter of the attached document has expressed no desire to withhold any information contained therein. Therefore, this material may now be made publicly available.
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J. M. Felton, Director Division of Rules and Records Office of Administration
Attachment:
As stated I
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. Carolina Power & Light Company g ggg4 SERIAL: NLS-84-015 Mr. James P. O'Reilly, Regional Administrator United States Nuclear Regulatory Commission Suite 2900 101 Marietta Street, NW Atlanta, CA 30303 -
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 EMERGENCY PLANNING
Dear Mr. O'Reilly:
In accordance with 10CFR50, Appendix E, Carolina Power & Light Company hereby transmits one copy of recent revisions to the Brunswick Steam Electric Plant Emergency Procedures. A list of the, revisions to the Plant Emergency Procedures is attached for your use.
If you have any questions on this subject, please contact our Licensing Staff.
Yours very truly,
'M -- r _
S. . Zi erman M ger Nuclear Licensing Section WRM/pgp (9281WRM)
Enclosures cc: Mr. D. O. Myers (NRC-BSEP) l Mr. M. Grotenhuis (NRC)
Document Control Desk (2 Copies)
U. S. Nuclear Regulatory Commission Washington, DC 20555 l
l M 4F l
lpb 411 Fayetteville Street
- P. O. Box 1551
- Raleign, N. C. 27602 0